RETRAN analysis of the Peach Bottom turbine trip tests
Journal Article
·
· Nucl. Technol.; (United States)
OSTI ID:5273885
The RETRAN system thermal-hydraulics analysis code has been used to model a series of three turbine trip tests. These three tests were performed at the Peach Bottom Unit 2 (PB2) boiling water reactor (BWR) during April 1977. A detailed description of this analysis including sensitivity studies using RETRAN-01 has been issued by the Electric Power Research Institute (EPRI). Additional analysis using RETRAN-02 is described. 8 refs.
- Research Organization:
- EPRI, Palo Alto, Calif, USA
- OSTI ID:
- 5273885
- Journal Information:
- Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 54:3; ISSN NUTYB
- Country of Publication:
- United States
- Language:
- English
Similar Records
Evaluation of RETRAN-02 options with Peach Bottom data
RETRAN-3D MOD003 Peach Bottom Turbine Trip 2 Multidimensional Kinetics Analysis Models and Results
Peach Bottom turbine-trip Test 3 analysis with RELAP5 code
Journal Article
·
Sun May 01 00:00:00 EDT 1983
· Nucl. Technol.; (United States)
·
OSTI ID:5316055
RETRAN-3D MOD003 Peach Bottom Turbine Trip 2 Multidimensional Kinetics Analysis Models and Results
Journal Article
·
Tue Apr 15 00:00:00 EDT 2003
· Nuclear Technology
·
OSTI ID:20826839
Peach Bottom turbine-trip Test 3 analysis with RELAP5 code
Conference
·
Fri Dec 31 23:00:00 EST 1982
·
OSTI ID:5701557
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
BWR TYPE REACTORS
COMPUTER CALCULATIONS
COMPUTER CODES
ENRICHED URANIUM REACTORS
MACHINERY
PEACH BOTTOM-2 REACTOR
POWER REACTORS
REACTOR SAFETY
REACTORS
SAFETY
STEAM TURBINES
TRANSIENTS
TURBINES
TURBOMACHINERY
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
BWR TYPE REACTORS
COMPUTER CALCULATIONS
COMPUTER CODES
ENRICHED URANIUM REACTORS
MACHINERY
PEACH BOTTOM-2 REACTOR
POWER REACTORS
REACTOR SAFETY
REACTORS
SAFETY
STEAM TURBINES
TRANSIENTS
TURBINES
TURBOMACHINERY
WATER COOLED REACTORS
WATER MODERATED REACTORS